2CAN128706, Monthly Operating Rept for Nov 1987
| ML20195H036 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/30/1987 |
| From: | Enos J, Harrison D ARKANSAS POWER & LIGHT CO. |
| To: | Bassett H NRC, NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 2CAN128706, NUDOCS 8801140333 | |
| Download: ML20195H036 (6) | |
Text
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OPERATING. DATA REPORT DOCKET NO:
50-368 OATE:
November,-1987 COMPLETED BY:D. F. Harrison TELEPHONE:
(501) 964-3743 OPERATING STATUS 1.
Unit Name:
Arkansas Nuclear One - Unit 2 2.
Reporting Period:
November 1-30, 1987 3.
Licensed Thermal Power (MWt):
2,815 4.
Nameplate Rating (Gross MWe):
942.57 5.
Design Electrical Rating (Net MWe):
912 6.
Maximum Dependable Capacity (Gross MWe):
897 7.
Maximum Dependable Capacity (Net MWe):
858 8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
9.
Power Level To Which Restricted.
If Any (Net MWe):
None 10.
Reasons For Restrictions.
If Any:
None MONTH YR-TO-DATE CUMULATVE~
11.
Hours in Reporting Period....
720.0 8,016.0 67,344.0 12.
Number of Hours Reactor was Critical.....................
696.8 6,971.4 48,978.1 13.
Reactor Reserve Shutdown Hours........................
0.0 0,0 1,430.1 14.
Hours Generator On-Line......
687.6 6,937.7 47,649.4 15.
Unit Reserve Shutdown Hours..
0.0 0.0 75.0 16.
Gross Thermal Energy Generated (MWH)........................
1,745,421.0 18,901,406.0 122,770,521.0 17.
Gross Electrical Energy Generated (MWH)..............
578,720.0 6,233,615.0 40,306,391.0 18.
Het Electrical Energy Generated (MWH)..............
550,921.0 5,942,136.0 38,356,883.0 19.
Unit Service Factor..........
95.5 86.5 70.8 20.
Unit Availability Factor.....
95.5 86.5 70.9 21.
Unit Capacity Factrr (Using MOC Net)..............
89.2 86.4 66.4 22.
Unit Capacity Factor (Using DER Net)..............
83.9 81.3 62.5 23.
Unit Forced Outage Rate......
4.5 13.5 14.9 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
A 72-day refueling outage is scheduled to begin February 12, 1988.
25.
If Shut Down At End of Report Period.
Estimated Date of Startup:
26.
Units in Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
'I 8801140333 871130 l
PDR ADOCK 05000368 R
a - :.
AVERAGE DAILY UNIT POWER LEVEL DOCKET N0; 50-368 UNIT'.
Two DATE:
November, 1987 COMPLETED BY: D. F. Harrison TELEPHONE:
(501) 964-3743 _
MONTH November, 1987 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1.............
633 2............
634 3.............
747 4.............
889 5.............
814 6.............
621 7.............
620 8.............
613 9.............
619 10............
627 11............
763 12............
894 13............
895 14............
183 15...........
67 16............
835 17............
891 18............
893 19............
893 20............
893 21............
894 22............
893 23............
891 24............
889 25............
893 26............
893 27............
893 28............
895 29...........
895 30............
894 31............
AVGS:
765 INSTRUCTION On this format, list the average daily unit power level in MWe-Net for each day in reporting month.
Compute to the nearest whole megawatt.
('
s NRC MONTHLY OPERATING REPORT j
OPERAT:1G
SUMMARY
NOVEMBER 1987 UNIT TWO e
r The unit began the month operating at reduced power-(approximately 70%) to allow for condenser tube leak searches.
The leak was found, and power was escalated to 100% on the third.
At 1743 hours0.0202 days <br />0.484 hours <br />0.00288 weeks <br />6.632115e-4 months <br /> on the fifth, a power reduction to about 70% power was begun due to a condenser tube leak.
The leaking tubes were located and a power escalation was begun on the eleventh.
The unit reached 10'% power at 0050 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> on the twelfth.
At 0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br /> on the fourteenth, the reactor tripped following a turbine trip due to high vibration on the #9 turbine generator bearing.
A unit startup was initiaced, and a reactor trip occurred with the reactor subcritical.
Another startup was subsequently begun, and the turbine was tied on line on the fifteenth at 1357 hours0.0157 days <br />0.377 hours <br />0.00224 weeks <br />5.163385e-4 months <br />.
The unit reached 100% power at 1025 hours0.0119 days <br />0.285 hours <br />0.00169 weeks <br />3.900125e-4 months <br /> on t',ie sixteenth, where it remained through the end of the month.
d l
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UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT FOR NOVEMBER, 1987 DOCKET N0 50-368 UNIT NAME ANO Unit 2 DATE November, 1987 COMPLETED BY D. F. Harrison TELEPHONE 501-964-3743 Method of Licensee Cause & Corrective Duration Shutting Event System Component Action to No.
Date Type (Hours)
Reason 2 Down Reactor 3 t
Report #
Coded Code 5 Prevent Recurrence 8705 11/01/87 F
71.2 A
5 N/A SG TBG Power reduced to search for a main condenser tube leak.
8706 11/05/87 F
151.1 A
5 N/A SG TBG Power reduced to search for a main condenser tube leak.
8707 11/14/87 F
52.9 A
3 2LER-87-008 TB GEN Turbine trip followed by reactor trip due to high vibration on the #9 Turbine Generator bearing.
8708 11/14/87 F
7.8 F
3 2LER-87-009 NA NA Reactor trip whle subcrite cical caused by Group 4 insertion with CPC's bypassed 1
2 3
4 F:
Forced Reason:
Method:
Exhibit G - Instructions S:
Scheduled A-Equipment failure (Explain) 1-Manua l for Preparation of Data B-Maintenance or Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File (NUREG-D-Regulatory.7estriction 4-Continuation 1022)
E-Operator Training &
5-Load Reduction License Examination 9-Other 5
F-Administrative Exhibit I - Same Source G-Operational Error (Explain)
H-Other (Explain) w
. s >
DATE: November, 1987 REFUELING INFORMATION 1.
Name of facility:
Arkansas Nuclear One - Unit 2 2.
Scheduled date for next refueling shutdown.
February 1988 3.
Scheduled date for restart following refueling.
May 1988 4.
Will refueling or resumption of operation thereafter requira a technical specification change or other license amendment?
If answer is yes, what, in general, will there be?
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?
Yes (see paragraph 5).
Reload fuel design and core configuration review is under way.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
Technical Specification change requests have been submitted.
6.
Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
A rebris resistant, extended solid end cap design will be used in the Fresh Fuel batch for cycle 7.
7.
The nuniber of fuel assemblies (a) in the core and (b) in the spent fuel storage pool, a) 177 b) 289 8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies, present 988 increase size by 0 l
9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
DATE:
1999 (Loss of fullcore offload capability)
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b ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 UTTLE ROCK. ARKANSAS 72203 (501)377-4000 December 15, 1987 2CAN128706 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.
20555 Attn:
Mr. Harold S. Bassett, Director Division of Data Automation and Management Information
SUBJECT:
Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 Monthly Operating Report
Dear Mr. Bassett:
The Arkansas Nuclear One - Unit 2 Monthly Operating Report for November 1987 is attached.
Very truly yours,
/
. Ted Enos, Manager Nuclear Engineering and Licensing JTE:MCS:gf Attachment cc:
U. S. Nuclear Regulatory Commission Region IV l
611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 ATTN:
Mr. Robert D. Martin Regional Administrator U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 ATTN:
Mr. James M. Taylor, Director Office of Inspection and Enforcement 4
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